IR 05000313/1980009
| ML19321B251 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/11/1980 |
| From: | Westerman T, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19321B249 | List: |
| References | |
| 50-313-80-09, 50-313-80-9, 50-368-80-09, 50-368-80-9, NUDOCS 8007300354 | |
| Download: ML19321B251 (5) | |
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O-U. S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report Nos. 50-313/80-09 50-368/80-09 Docket No. 50-313 License No. DPR-51 50-368 NPF-6 Licensee: Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203
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Facility Name: Arkcnsas Nuclear One (ANO), Units 1 and 2 Inspection at: AN0 Site, Russellville, Arkansas Inspection Conducted: May 27-30, 1980 Inspector:
CL4A d d,
btll14Sc, L. A. Yandell, Re' actor Inspector Q Date'
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Accompanying Personnel:
P. G. Wisco, Nuclear Technologist, Philippine Atomic Energy Commission Approved By:
7 elbL MA Le n,, & fc T. F. Westerman, Chief, Reactor Projects Section Date Inspection Summary:
Inspection conducted during the period of May 27-30, 1980 (Report No. 50-313/80-09)
i Areas Inspected:
Routine, unannounced inspection of design changes and modifica-tion program, and test and experiment program.
The inspection involved 16 inspector-hours on site by one (1) NRC inspector.
Result: Within the two areas inspected no items of noncompliance or deviation were identified.
Inspection conducted during the period of May 27-30, 1980 (Report No. 50-368/80-09)
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Areas Inspected:
Routine, unannounced inspection of design changes and modification program, and test and experiment program.
The inspection involved 16 inspector-hours on site by one (1) NRC inspector.
Results: _ Within the two areas inspected, one apparent item of noncompliance
~ (Infraction - failure to adhere to procedures, paragraph 3) was noted.
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DETAILS 1.
Persons Contacted J. P. O'Hanlon, AN0 Plant Manager
- G. H. Miller, Engineering and Technical Support Manager
- F. Foster, Operations and Maintenance Manager
- T. N. Cogburn, Plant Analysis Superintendent E. C. Ewing, Plant Engineering Superintendent B. Austin, Assistant Supervisor, Office Services S. Wages, Document Control Clerk J. C. Garrett, Material Management Supervisor J. Ray, QC Engineer R. West, Unit 2 I&C Supervisor D. Thompson, I&C Technician
- Present at exit interview.
2.
Design Changes The inspector reviewed the following documents related to design changes to determine that procedures have been established for requesting, re-viewing, approving and implementing plant design changes.
I a.
Procedure 1000.13, Control of Station Modifications b.
Procedure 1032.01, Design Control c.
Procedure 1032.03, Drawing Control
- These procedures describe a design change program that has been in effect for about six months, with some of the supporting procedures such as 1032.02, " Changes to Design Packages" still to be issued.
The following documents were reviewed to determine that the design change program was being performed in accordance with approved procedures.
i Plant Engineering Action Requests (PEAR), No's 1-300 a.
b.
Design Change Packages (in progress)
79-1032 Reactor Protection System Anticipatory Trip 80-1008 Modifications to S/G EFW Nozzles 80-1010 Pressure Switch Tie-in Points on Main Turbine /Feedwater Pump Turbine Control Oil Systems (for DCP 79-1032)
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80-1019 Replace Traps, PSV-4812 in Gaseous Radwaste System
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80-1027 Provide Alternate 120V Power Supply to NNI System (Crystal River III)
80-1055 Reset Function for SLBIC and Modification to CV 2680 and CV 2630 80-1056 Move Core Flood Tanks M0V's to Emergency Diesel 80-1057 Add Decay Heat Isolation Reset Controls in Control Room 80-2011 Change Relay Contacts from ESFAS (Heater Drain Pumps)
80-2017 Pressurizer Spray Valve Control 80-2021 S/G Level Indication and EFW Control 80-2037 Valve Reset Feature, Valve 2CV-1010-1, 2CV-1060-2, 2CV-1024-1, and 2CV-1074-1 80-2038 Modification to Hand Switches on Remota Shutdown Monitoring Panel 80-2045 Boric Acid Makeup Pump Auto Control 80-2062 Replace 2SV-1016-2 and 2SV-1066-2 (S/G Blowdown Isolation)
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Design Change Packages (completed).
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80-2008 Change Level Switch 2LS-4861A 80-2014 Modification of Detent System on Coupling Mechanism 2CV-5091 and 2CV-5093 80 2020 Control Switches 2SV-5833-1 and 2SV-5843-2 Modifications d.
PEAR Log, all entries f
Design Change Package Logs, (Unit-1 and Unit 2), all entries e.
Minor administrative inconsistencies were identified in procedure 10C" 13,
- and these are being corrected in the next revision presently undergoing review and approval.
DCP 80-2020 was found to be incomplete (FCN #1 of the " Test Copy" was missing), although it had been filed in the vault as a completed package.
This was corrected by the licensee and verified by the inspector prior to the exit meeting.
The. licensee is aware that the precedures failed to catch this, and intends to take action to prevent a similar occurrence..This will remain 'an open item until this action has been completed and reviewed.
(0 pen item 368/80-09-02; 313/80-09-01)
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f No items _ of noncompliance or deviation were found.
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The' inspector reviewed the procedure for handling temporary modifications
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(jumpers and bypasses) and examined several entries in the Unit 2 Jumper
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and Bypass Log to determine that the procedure was being properly implemented.
As a result of this review, the inspector found the following:
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entries 2/79/134 to*2/79/142 and 2/79/148 to 2/79/151 were being carried as open items after the jumper / bypass had been removed,
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duplicate tags (2/79/148 to 2/79/151) were issued for two separate tagouts, and c.
completed pages of the log had not been forwarded for filing.
I This is a failure to adhere to the procedures established in procedure 11005.04, " Control and Use of Bypass and Jumpers," and constitutes an apparant item of noncompliance at the infraction level.
(368/80-09-01)
No additional a'dverse findings were identified.
4.
Test and Experiments Program The inspector reviewed procedure 1000.06, " Procedure Review, Approval and Revision Control", to determine that a formal method has been established to handle requests or proposals for conducting plant tests and experiments involving safety-related: components, systems or struc-tures, or modes-of operation-different from those described in the
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FSAR, including review and approval, assignment' of responsibility,
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, safety evaluation pursuant to~ 10 CFR 50.59, conduct of the test, and timely reporting to the NRC.
No tests or experiments have been proposed or ~ conducted under the revised procedure 1000.06, but
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WP2-74, Power Ascension Testing Following Reactor Internals Inspection, (Appendix A-Th Anomaly) was reviewed against the current procedure and no items of noncompliance or deviation were found.
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Plant Tours--
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l During tours of various areas of Unit'2, it was noted and brought to the
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licensee's attention at the exit meeting that equipment and material were seen laying around in passageways and that'the matter of plant cleanliness needed to be addressed.
The licensee indicated an awareness
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of the problem and is working to correct.the situation. No. items of noncompliance or deviation were identified.
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Exit' Interview
~ An exit meeting was conducted on May 30, 1980 with G. H. Miller.and other.
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L members-of the plant staff as indicated in paragraph 1, to summarize the scope of the-inspection and the findings.
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